Elsheikh Nassreldeen A A
Al-Baha University, College of Science&Arts in Al-Mikhwah, Department of Physics, P.O. Box 1988, Al-Baha, Saudi Arabia.
Appl Radiat Isot. 2020 Feb;156:109012. doi: 10.1016/j.apradiso.2019.109012. Epub 2019 Dec 2.
Monte Carlo simulations (MCNP) were carried out to model suitable Cf-based gamma transmission and neutron attenuation geometries to evaluate the gamma-ray shielding features and neutron attenuation capabilities for AlO, MgF, Fluental and AlF, as fast neutron moderators of potential interest in Cf-based Born Neutron Capture Therapy (BNCT) facilities. The mass attenuation coefficient (μ/ρ), Half-Value Layer (HVL), Mean Free Path (MFP) and gamma transmission factor (I/I) for AlO, MgF, Fluental and AlF were simulated at gamma energies, 0.3 MeV, 0.364 MeV, 0.662 MeV, 1.25 MeV and 7.12 MeV. The MCNP simulated μ/ρ values were compared to theoretical XCOM values and good agreement was observed. The ratio of total thermal neutron flux to the total fast neutron flux (φ /φ ) and the total flux of gamma rays (φ ) resulting from thermal neutron capture (n,γ) reactions, were simulated and compared as a function of thickness for the four sample moderators. The values of the effective fast neutron removal cross section Σ (cm) for the four sample moderators were calculated and compared.
进行了蒙特卡罗模拟（MCNP），以对合适的基于锎的伽马射线传输和中子衰减几何结构进行建模，从而评估氧化铝（AlO）、氟化镁（MgF）、氟代烃（Fluental）和氟化铝（AlF）作为基于锎的硼中子俘获疗法（BNCT）设施中潜在感兴趣的快中子慢化剂的伽马射线屏蔽特性和中子衰减能力。在0.3兆电子伏、0.364兆电子伏、0.662兆电子伏、1.25兆电子伏和7.12兆电子伏的伽马能量下，模拟了氧化铝、氟化镁、氟代烃和氟化铝的质量衰减系数（μ/ρ）、半值层（HVL）、平均自由程（MFP）和伽马射线传输因子（I/I）。将MCNP模拟的μ/ρ值与理论XCOM值进行比较，观察到良好的一致性。模拟并比较了四个样品慢化剂的总热中子通量与总快中子通量之比（φ /φ ）以及热中子俘获（n,γ）反应产生的伽马射线总通量（φ ）随厚度的变化。计算并比较了四个样品慢化剂的有效快中子去除截面Σ（厘米）的值。
